Tritium Permeation Characterization of Materials for Fusion and Generation IV Very High Temperature Reactors

S. Thomson; K. Pilatzke; K. McCrimmon; I. Castillo; S. Suppiah

doi:dx.doi.org/10.13182/FST14-T58

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Home / Publications / Journals / Fusion Science and Technology / Volume 67 / Number 3

Tritium Permeation Characterization of Materials for Fusion and Generation IV Very High Temperature Reactors

S. Thomson, K. Pilatzke, K. McCrimmon, I. Castillo, S. Suppiah

Fusion Science and Technology / Volume 67 / Number 3 / April 2015 / Pages 475-478

Proceedings of TRITIUM 2013 / dx.doi.org/10.13182/FST14-T58

First Online Publication:March 6, 2015

Updated:April 2, 2015

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A description of the work performed to set up an apparatus to measure permeation rates of hydrogen and tritium in 304L stainless steel is presented. This is in preparation for future work to find and qualify candidate materials resistant to tritium permeation in various advanced nuclear systems.